© 2020 Energy M Gryaznevich and Tokamak Energy Ltd. Team uinA Webinar 14September 2020 FusionCAT Faster Fusion Innovations through © 2020 Tokamak Energy (3) No longer No in use. (3) The International Thermonuclea (2) Under construction. (1) Note: are operating unless indicated otherwise. ConventionalTokamak San Diego, CA DIII-D Saskatoon, SK STOR-M uinRsac Public Tokamaks Fusion Research– r Experimental Reactor (“ITER” Reactor r Experimental Madison, WI Pegasus lao C-Mod Alcator Cambridge, MA Cambridge, LTX / NSTX / LTX Princeton, Princeton, NJ (3) ) megaproject is supported by China, the European Union, India, • • ITER Cadarache, FR However, progress towards isconstrained Fusion research advancingis (1)(2) Oxford, UK Oxford, MAST Lisbon, Lisbon, PT ISTTOK / WEST / Oxford, UK Oxford, JET Lausanne, CH COMPASS Prague, CZ TCV Garching, Garching, DE Frascati, IT ASDEX FTU SST-1 /ADITY Gandhinagar StPetersburg, RF GLOBUS-M Moscow T15-M (1) , IN Kurchatov, Kurchatov, KZ Japan, Korea, Russia and the UnitedJapan, States. KTM Chengdu, CN HL-2 Hefei, CN EAST Daejeon, Daejeon, KR KSTAR Kasuga, Kasuga, JP QUEST JT-60SA Naka, JP (1) 2 © 2020 Tokamak Energy Los Angeles, Los CA Vancouver, BC Non-Tokamak Non-Tokamak Technology Spherical Tokamak Tokamak Conventional Orange County, CA uinDvlpet–PrivateFunding – Fusion Development Cambridge, MA Cambridge, Oxford, UK Oxford, Oxford, UK Oxford, • • Roadmapping reactor andthen used gaps At TE,we have identifiedthe technologies andFusionIndustry funded Fusion research isto develop omnga fpiaeyandpublicly Common goal ofprivately needed to create commerciala fusion as anapproach our chart path. Langfang, Langfang, PRC Technology keytechnology 3 © 2020 Tokamak Energy The emergenceof theFusionIndustry Private- Fusion CompetitiveLandscape https://www.fusionindustryassociation.org/ 4 © 2020 Tokamak Energy The emergenceof theFusionIndustry Private- Fusion CompetitiveLandscape Mumgaard,CFS 5 © 2020 Tokamak Energy Our approachis basedonInnovative Physics andTechnology Squashed shape, compact Highly efficient, from 12% in DIII-D to 40% DIII-D in 12% from Spherical Tokamaks in START/NSTX smaller, cheaper, faster high E E  : requirements cooling cryogenic Lower High current at high field Superconductors High Temperature developmentof fusionpower. believeis thekey to superconductors that we high temperature spherical tokamak shapewith combinationthis It is ofthe 6 © 2020 Tokamak Energy Our principles: • • • • a faster way to get to acommercially viable device We rely on the DEMO, STEP). Strong focus on Our approach has Use of Collaboration progress at a multiple compact devices Together wecan make Fusion Faster! faster pace in development of Fusion Science and Technologies same physics industrial ‘deliverability’ common groundwith and behind the fusion magnetic concept …butwe have lower risk financial and demonstrators to validate and modelling mainstream Tokamak Fusion (e.g. and cost . of the commercial device ITER , 7 © 2020 Tokamak Energy Our developmentprinciples: • • • • enough test beds, etcR&D use To need journey, we have asked ourselves whether it islikely to be pre seeking cast iron guarantee that technology availableis at the In aworld where technology advances at ever increasing speed, probable established The long term nature offusion development means that many of t technology isdeployed. Approach to Technology Development We have consciously embraced risks around the development of it innovations along theway. technological advances. technologies efficiently, we need to reduce the build time andhave will be out-of-dateby thetime the fusion sent

beginning rather than highly oday’s when we of our 8 © 2020 Tokamak Energy • • What Innovation?is Our approachis basedonInnovative Physics andTechnology orto a apply new technology to improve what’s currently avail – eve a novel way to usean existing processservice, or product – Innovation doesn’thaveto be abrand-new invention; infact, i ornon-profitin business,publicservices, sectors.” knowledge ofideas for thedevelopment ofproducts, or services UK Research and Innovation (UKRI) recognises The project must result in a product/process/service that c is - The projected end-result must be above thecurrent state-of-th - The project must be disruptive in its intended market - innovation as “the application of https://www.tbat.co.uk/ t very rarely is! Itcan be ommercially viable n ina different industry able. processes – whether whether processes– e-art available 9 © 2020 Tokamak Energy TokamakEnergy Technology Roadmap to FasterFusion 10 © 2020 Tokamak Energy • • • • drive) wave current > to milliseconds (extended pulse Toroidal Field: Poloidal Field: Field: • Paperspublished showing 24.4T First T0-highest TF inSTs ST40 - Improvements in performance 20s T510S2 . T512ST40 1.0 ST25 1.2 ST25 1.1 ST25 1.0 with micro- 2012 2013 2014 2015 2014 2013 2012 full-HTS peak field on peak field coil (22T in thebore) inpure-HTS magnet of of a few Copper Copper Low Achievements &Progress to date tokamak Stable operations Industrial Field Toroidal Poloidal Field: Field: HTS PFcoils, : Copper tokamaks do not have to behuge Low HTS with TF confirmed supported 29 HTS magnets First World Toroidal Field: Poloidal Field: Field: -hour plasma, Tokamak with RF Low HTS HTS all 2016-19 temperatures in keV first campaign: ST40 Toroidal Field: Poloidal Field: Toroidal Field: from to achieve Fusion achieve to m/c formation - highest field Spherical Tokamak Copper Copper I pl > 0.5MA, > 2x10 0.5MA, 2 T -range.I pl > 400 20 m kA -3 , 1 sec flat sec 1 Autumn forPlans diagnostics, divertor, PSUs, Significant Toroidal Field: Poloidal Field: Toroidal Field: + DNBI new PF coils,new 2020 -top at 3 T,2 ST40 2.0 2.0 ST40 more upgrades of bioshield. bioshield. Copper LN2 Copper LN2 3.0 T 2020: NBI 11 © 2020 Tokamak Energy INNOVATIONS 12 © 2020 Tokamak Energy Threeinnovations: main • • • • Plus: Li conditioning, Lidivertor, low recycling regime, high HTS Magnets can adoptinnovations: more start-up, new CDandheating, wall and divertor materials - Fusion Power Plant Magnetic reconnection Spherical Tokamak - cheaper and quicker to build. Innovations are indeed easier to test and use in smaller device Innovations on the Way to Fusion Power – solution for solution highfield,sobetter performance and economics – as asolutionto CompactReactor andModularapproach for as formation andheating method. field side EBW for welcome! We s that are also 13 © 2020 Tokamak Energy opc uinpltpaticuigdaigu Ls ftepicplin principal the of “List a up the drawing from including plant pilot fusion compact US the In STs>. in competition, we are complimentary. Idon’twant to illuminat We are very pleased to work with them projects. asoften itispossible. as We are not e any ofthem

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p = 3.5 /aB ~ T E 2 B • • FUSION POWER”,FUSION TECHNOLOGYVOL. 33 JAN. 1998 TOKAMAK SPHERICAL PATHRonStambaugh,“THE TO t determine its size”. great that the physics of thisdevicenot will “Apparently the high beta potential ofthe ST is so 4 ,V, Field alreadyincreasedtoField 2T,this year 3T be will and already demonstratedfirstin experiments Improvements performancein withincreased field so volume(reactorsize) canbereduced! latest on ST40 16 © 2020 Tokamak Energy • in Observed sharpincrease inT GT2 simulations Improvement in confinement at higher Toroidal Field reduction in transport at higher toroidal field inanST: i and W therm at B at - - - t ~ 1Tmay beconnected withthe predicted higher B arethese modes; microtearing diffusivity isdominatedby one Threshold no betaat orshape dependence highfield At electrostatic low observed in ST40, ~ 1 - 1.5 T 1.5 in ST40,observed ~1- magnetic field the mixing lengthmixing field the magnetic t , diffusivity thenbeingdominatedby toroidal field isquite low, closeto twisting modes. electromagnetic stabilisedat 17 © 2020 Tokamak Energy • Fusion power • Physics is good. Engineering of highfield inSTis a real challenge! plasma volume Increase inbeta allows significant reduction in TE PathtoFusion, HighfieldST? why Efficiency Field strengh Volume 18 © 2020 Tokamak Energy HTS FOR TOKAMAKMAGNETS 19 © 2020 Tokamak Energy Arguments: • • • • • • Only solution for solution Only >20Tonconductor Supply chain improving the time all chain Supply performanceGood neutronsunder Good mechanical properties Can tolerateheatingLTS some (while willquench!) for needed compactreactors power – cryo Reductionin Why HTS ? 20 © 2020 Tokamak Energy Why HTS? JET,ITER, European DEMO: 21 Progress:

© 2020 Tokamak Energy • • • Choice of tape => done => tape of Choice ant researchon-going Magnets– done => cable of Choice - 6 tapes 6 checked,all good, productionquantity of needed andg - farrelevant aspossible under operatingmagnet conditions. + PF prototype TF under construction.is Itwill testkey tech - studies Quench and quench protection - 20+coils tested,20T @20K > - joints, feedsall hassolutions => - patented owndesign, our - cables upto 100kA testedat NIFS, canwe work at lowercurre - H T S

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L a per week b o r a t o r y © 2020 Tokamak Energy • Scale up plan for fusion: • • • • • • • • • • No need for tapelong lengths (~20misOK) Defect and damage tolerant High voltagenot insulationrequiredis Survives repeatedfast (LTS-like)quenches 24.4 T achieved conduction cooled at 21 K and (no assembly disassemblysoldering) Simple Modular, robusthigh &scalable magnets HTSfield Retainquench protection benefitswith of fast ramp capability No twisting / transposition (enables > 300 A/mm 300 transpositiontwisting > / No (enables novelpartial insulation -resistant insulation HV requirednot simple large coil manufac Ex-situ cooling & structural– support Our QA coil technology is ready also for non-fusion application ! H T S

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L t d QA Dochart room, 16:45 2-LO-FH-02S 3 Sept 2019 16.5 T @23 K FrankenCoil R Slade 24.4 T @21 K Demo3 © 2020 Tokamak Energy FORMATION ANDHEATING MAGNETICRECONNECTIONS FOR 25 • • •

© 2020 Tokamak Energy as used on STARTas used and MAST magne using achieved canbe This field magnetic to 90%),thususing to transfer It ispossible the externallyvessel, by on based is confinement Magnetic • • • predictions. First results from ST40alreadyconfirm these (nT) conditions plasma in from START, Japanese MASTdevices, and astrophysics60-70th in in developed Reconnection hasbeen theory to reconnection~ B Accordingthatto predicts theory heating due Better use of Magnetic Field: reconnection heating ST40 should showshould with temperatureswith ~10keV 2 , and experimental, and data magnetic energy applied magnetic field. field. magnetic applied burning containmentof hotplasmaand not only for the containment tic reconnections during mergin reconnectionsduring tic directly into the plasma directlyinto rdcin First results: scalingconfirmed! Predictions , but also thermal energy g- insolationof theof itfromthewall vacuum compression formation of the tokamak plasma thetokamakof formation compression for the plasma with a very high efficiency(up high verya with heating . 26 © 2020 Tokamak Energy START • Recently studied indetail onMAST, UTST,VEST, ST40. Firstused onSTART, at Culham, in1991. Successfullyapplied o • 3 stages: compression - merging (reconnection) - around plasma coils - Merging ng g - compression plasma formation n MAST to achievefirst plasma in1998. • • keV-range temperatures without CS assistance Plasma currents 200-500kA MAST 27 • • •

© 2020 Tokamak Energyergy ~1 keVisrough obtainedin agreement MAST with &ST40 results the depositio with Assuming reconnectionMW powerheatingof 20 Alfven in co-directionpoloidalenergyand are mainly running MontesimulationsCarlo arethe assumptiontha basedon NFREYA – Tomerging-compression model process codes reconnection produced by Orbits oftheions eoncinhaig–injection fastof ions Reconnection heating –

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reconnection heating, Time evolution of T

n D(r) and a heating time of 3 ms, temperaturems, 3 of time T aheating and of D(r) n t the ions formedt the reachthe reconnectionduring the i due to haveused. been TSC Time evolution of T MAST and of T i on ST40 e,i on i 28 © 2020 Tokamak Energy MODULAR APPROACH 29 © 2020 Tokamak Energy • • • • improve reliability by thecheap reservation, to useeconomy of The approach permits saving time and resources forneeded thed maintenance to-module way, providing In all modular approaches, regular maintenance necessary set is modules consist of several low power modulesandthe auxiliaries are sh In this fusion powerfusion plant. TokamakFrom 2014, Energy Ltd.is developinga – Chuyanov, FED Gryaznevich, JournalofPhysics:Gryaznevich, Conference Series new alternative route Modular PowerModular Plant 122 (2017) 238 high availability the economically feasible fusion power, plant will of thepower plant and 591 modular design (2015) 012005; (2015) 012005; ared between mass production 30 off lineinamodule- evelopment, to lower cost of of a • •

© 2020 Tokamak Energy • lead to increase ofthecapital cost of the plant. the plant and “ Modular approach combines advantages of“ DEMO) andtheriskoffusiondevelopment some common auxiliary systems. This decreases the cost ofproto A modularfusionplant consisting of several At the same time it permits to design very efficient ST-based Many small unitsisattractive for manufacturers – - be availability High due to reduced durationfirst ofthe wall ch - - Units can Units - serviced in turn serviced Modular Approach for Power plant share economy of massproduction start-up (gyrotrons) and remoteaccess facilities, andahotce , so electricity supply canso electricity be maintained;, . Chuyanov,FED, 2015 compact, low-power highfieldST modules “ for fusioncore oftheplant anddoesnot economy of scale sustainable chain supply ange andmaintenance. fusion power plant ” for conventional partof types (onemoduleisa ; ll for maintenance; Modules can : and 31 © 2020 Tokamak Energy • aspect ratios between 1.65